ML19326B903
| ML19326B903 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/07/1976 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326B896 | List: |
| References | |
| NUDOCS 8004180627 | |
| Download: ML19326B903 (21) | |
Text
_ _ _ _ _ _ _.
6Y UNITED STATES c'
~4 NUCLEAR REGULATORY COMMISSION CASHINGTON, D. C. 20566 ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 l
ARKANSAS NUCLEAR ONE - UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated September 30, 1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of i
the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the i
common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
- R7 1
8004180
J 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
3.
This license amendment is effective ninety (90) days following the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
( 3 1
/,,,,.,m S,'fe.i-vot.+r-Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: December 7,1976
ATTACHMENT TO LICENSE AMENDMENT NO.16 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace existing pacts-117 through 139 of the Technical Specifications contained in Appendix A to the license with the attached revised pages 117 through 134. The changed areas on the revised pages are identified by marginal lines.
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Superintendent of Power Plant shall be responsibic for overall facility operation.
In his absence, the Assistant Superintendent of Power Plant shall assume all responsibility and perform all duties of the Superintendent of Power Plant.
If both the Super-intendent of Power Plant and his assistant are absent, these respon-sibilities and duties are assumed by the Supervisor of Plant Operations followed by the Technical Support Engineer.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility managenant and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2A and 6.2-2B and each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the licalth Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Supervisor of Plant Operations and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Committee shall function to advise the Super-intendent of Power Plant on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the:
Amendment No.16
- 117 -
TABLE 6.2-1 ARKANSAS NUCLEAR ONE MINIMlD1 SilIFT CREW COMPOSITION #
UNIT 1 LICENSE COLD AND REFUELING CATEGORY ABOVE COLD SlitTTDOWN SHUTDOWNS J
SOL 1
1*
OL 2
1 NON-LICENSED 2
1
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling, supervising refueling operations after the initial fuel loading.
- Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
Additional Requirements:
1.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
2.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
3.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
4.
All refueling operations after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuci Handling who has no other concurrent responsibilities during this operation.
- 118 -
Amendment No. 16
SENIOR VICE PRESIDENT PROD..TR ANS.
)
& ENGRG.
SAFETY REVIEW 3
QUALITY ASSURANCE COMMITTEE E
cv.MITTEE DIRECTOR POWER PRODUCTION 1
I ASST. DIRECTOR POWER PRODUCTION 1
MANAGER MANAGER MANAGER MANAGER OUALITY NUCLEAR NUCLEAR LICENSING ASSURANCE PROJECTS FUEL SUPERINTENDENT COMMITTEE ARKANSAS POWER G LIGliT COMlW;Y MANAGEMENT ORGANIZATION CllART ARKANSAS NUCLEAR ONE - IINIT 1 6.2_1 Amendment No.16 Uo.
.c
-.,__.,._.,...,_...,.._..__.,,,_,_,...,,,,,,,s
SUPERWTENDENT OF POWE9 PLANT CE AS$1STANT SUPT. OF POWER PL ANT
)
CE LSO SEE FIGilRE 6.2-2B I
I I
hg'g SUPVSR PLNT OPS 0.C. ENelNEER CE LSO l
i l
l 1
y3g CH EWih ENY H. P.
PERFORW ASST.SUPVSR PLT OP Q.C INSPEC TORS SUPVSR SUPVSR ENGR.
LSO i
SHIP T OP SUPY3R TRAINING COORDINATOR ASST. H P.
SUPv5R LSO PLANT OPER D
Lo RA0lO CLN. LAB.
CHECISTS CHEMISTS H. P.'s ASST PLNT OPER LO WSTd. p CONT.
OPER.
C - Degree or Equivalent Required AUX.
CE - Engineering Degree or fquivalent licquired L50 - Senior Opera'or Lleense Required LO - Operator License Required l
l l
ARKANSAS POliER G LICifT CO.
FUNCTIONAL ARKANSAS NUCLEAR ONE-UNIT 1 ORCANIM TION FOR FIGURE PLANT OPERATION 6.2 2A Amendment No.16 120 -
.I SEE FIGURE 6.2-2A
.g I
I l
stuPVSR* PLNT MAINT MLfCLE AR ENOR.
INSTR ME SU SR CE CE I
l I
I I
AS ST W AINT SUPYSR REACTOR REACTOR ASST lac ENOR.
TECH.
Supygg CC l
PLMT.WAJftf.
PLANT ELECTN.
REPRWN.
I8C TECN C - Degree or [quivalent Required CE - Engineering Degree or Equiv41cet Required L50 - Senior Operater Licente Re.iutreJ
)
LO - Operator License Required AltKANSAS IWI:R G LICl!T CO.
FUNCTIONAL ARKANSAS NUCLEAft ONF.-UNIT I ORGANIZATION FOR FIGURE PLANT OPERATION b.2 2B Amendment No. 16
- 121 -
Chairman:
Assistant Superintendent of Power Plant Memb er:
Technical Support Engineer l
Member:
Instrumentation 4 Controls Supervisor Member:
Supervisor of Plant Operations Member:
' Supervisor of Plant Maintenance Member:
Nuclear Engineer Member:
llealth P'..ysics Supervisor The Superintendent of Power Plant shall appoint an acting chair-man in the absence of the Assistant Superintendent of Power Plant.
ALTERNATES All alternate members shall be appointed in writing by the PSC Chairman 6.S.I.3 to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities at any one time.
MEETING FREQUENCY 6.S.I.4 The PSC shall meet at 1 cast once per calendar month and as con-vened by the PSC Chaiman or his designated alternate.
QUORUM 6.S.I.S A quorum of the PSC shall consist of the chairman and three members including aDernates.
RESPONSIBILITIES 6.S.I.6 The Plant Safety Committee shall be responsible for:
a.
Review of 1) all procedures.aquired by Specification 6.8 and revisions thereto, 2) any other proposed procedures or revisions thereto as detemined by the Superintendent of Power Plant to affect nuclear safety, b.
Review of all proposed tests and experiments that affect nuclear safety, Review of all proposed changes to the Appendix "A" Tech-c.
nical Soccifications.
d.
Review of all proposed changes or modifications to plant systems.
or equipment that affect nuclear safety, Investigation of all violations of the Technical Specifications i
e.
including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Superintendent of Power Plant, f.
Review of those Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification of the Commission.
Amendment No.16
- 122 -
g.
Review cf facility cparcticns to dstcet potential nuclear safety hazards, h.
Performance of special reviews and investigations and reports thereon as :,uested by the Superintendent of Power Plant.
i.
Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Superintendent of Power Plant.
j.
Review of the Emergency Plan and impicmenting procedures and shall submit recommended changes to the Superintendent of Power Plant.
Atml0RITY 6.5.1.7.1 The Plant Safety Committee shall:
a.
Recommend to the Superintendent of Power Plant written approval or disapproval of items considered under 6.5.1.6(a) through (d) above, b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question.
6.5.1.7.2 In the event of a disagreement between the recommendations of the Plant Safety Committee and the actions contemplated by the Superintendent, the course determined by the Superinten-dent to be more conservative will be followed.
Records of the disagreement will be sent for review to the Assistant Director, Power Production and the Chairman of the Safety Review Committee by the Superintendent on the next working day.
RECORDS 6.3.1.8 The Plant Safety Committee shall maintain written minutes of each meeting and copies shall Pe provided to the Chairman of the Safety Reviet* Committee by the Superintendent of Power Plant.
6.5.2 Safety Review Committee (SRC)
FUNCTION 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiocnemistry Amendment No.16
- 123 -
d.
notc11urgy 1
c.
instrumen'.ation and control f.
radiological safety g.
mechanical and electrical engineering h.
environmental considerations
- i. other appropriate fields required by the unique characteristics of the nuclear power plant COMPOSITION 6.S.2.2 The SRC shall be composed of the:
Chairman: Director Power Production Member:
Asst. Director, Power Production Member:
Maintenance and Operations Coordinator Member:
Manager of Safety Member:
Arkansas Nuc1 car One Superintendent of Power Plant Member:
Representative from G.O. Chemistry Section Member:
Arkansas Nuc1 car One Nuc1 car Engineer Member:
Manager, Nuclear Fuci Member:
Radiation and licalth Physics Consultant Member:
Nuc1 car Safety Consultant Member:
Manager, Licensing In his absence, the Chairman shall appoint an Acting Chairman.
ALTERNATES 6.S.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activitics at any one time.
CONSULTANTS 6.S.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING FREQUENCY 6.S.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
QUORUM 6.S.2.6 A quorum of SRC shall consist of the Chairman or his designated alternate and five members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.
Amendment No.16 124 -
REVIEW 6.5.2.7 The SRC shall review:
a.
The safety evaluations for 1) changes to procedurcs, equip-ment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
Proposed tests or experiments which involve an unreviewed c.
safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or licenses, Violations of applicabic statutes, codes, r,egulations, orders, e.
Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected performance of plant ' equipment that affect nucitar safety.
g.
Reportabic occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.
h.
Reports and meeting minutes of the PSC.
AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
a.
The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The performance and retraining of all members of the plant management and operations staff, and the performance, training, and qualifications of new e. embers of the entire plant staff at least once per year.
c.
The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The Facility Emergency Plan and implementing procedures at least once per two years.
- 125 -
Amendment No. 16
o.
ThD Facility Security Plan and impicmenting procedures at least once per two years, f.
Any other area of facility operation considered appropriate by the SRC or the Senior Vice President (PT6E)
AUTHORITY ^
6.5.2.9 The SRC shall report to and advise the Senior Vice President (PT6E) on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of SRC activities sF. t1 be prepared, approved and dis-tributed as indicated below:
a.
Minutes of each SRC meeting shall be prepared, approved and forwarded to the Senior Vice President (PT6E) within 30 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 e, f, g and h above, shall be prepared, approved and forwarded to the Senior Vice President (PT6E) within 30 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President (PTSE) and to the management positions responsibic for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for Reportabic Occurrences:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.12.
b.
Each Reportabic Occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Coramission shall be reviewed by the PSC and submitted to SRC, the Assistant Director, Power Production by the Superin-tendent of Power Plant.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
1 a.
The facility shall be placed in at least hot shutdown within one hour, b.
The Nuc1 car Regulatory Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.36 and Specification 6.12.3.1 Amendme t No.16
- 126 -
n
1 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
6.8.2 Each procedure of 6.8.1 above, and changes trareto, shall be reviewed by the PSC and approved by the Superintendent of Power Plant prior to implementation and reviewed periodically as set 4
forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, c.
The change is documented, reviewed by the PSC and approved by the Superintendent of Power Plant within 14 days of 1
implementation.
Amendment No. 16
- 127 -
6.9 RECORD RETENTION 1
6.9.1 The following records shall be retained for at Icast five years:
a.
Records and logs of facility operation covering time interval at each power Icycl.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.
All Reportable Occurrences submitted to the Commission pursuant to Specification 6.12.3.
d.
Records of surveillance activities, inspections and calibrations required by the Appendix A Technical Specifications, e.
Records of reactor tests and experiments.
f.
Records of changes made to procedures required by Specifi-cation 6.8.1 g.
Records of radioactive shipments.
h.
Records of scaled source leak tests and results.
i.
Records of annual physical inventory of all source material of record.
6.9.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report, b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas.
c.
Records of gaseous and i quid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles, g.
Records of training and qualification for current members of the plant staff.
- 128 -
Anendment No. 16
i h,
R: cords' of in-scrvice inspections performed pursuant to these Technical Specifications.
i.
Recccds of Quality Assurance activitics required by Section 17 of the Quality Assurance Manual for Operations.
j.
Records of reviews performed for changes made to procedures or equipment or zeviews of tests and experiments pursuant to 10 CFR 50.59.
k, Records of meetings of the PSC and the SRC.
6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radi-ation exposure.
6.11 RESPIRATORY PROTECTION PROGRAM ALLOWANCE 6.11.1 Pursuant to 10 CFR 20.103(c)(1) and (3), allowance may be made for the use of respiratory protective equipment in conjunction with activitics authorized by the operating license for this facility in determining whether individuals in restricted areas are exposed to concentrations in excess of the limits specified in Appendix B, Tabic I, Column 1, of 10 CFR 20, subject to the following conditions and limitation.
a.
The limits provided in Section 20.103)a) and (b) shall not be
- exceeded, b.
If the radioactive material is of such form that intr.ke through the skin or other additional route is likely, individual expo-sures to radioactive material shall be controlled so that the radioactive content of a'ny critical organ from all routes of intake averaged over 7 consecutive days does not exceed that whi-h would result from inhaling such radioactive material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the pertinent concentration values provided in Appendix B, Tabic I, Column 1: of 10 CFR 20.
c.
For radioactive natorials designated "Sub" in the "!sotope" column of Appendix B, Tabic I, Column 1 of 10 CFR 20, the concentration value specified shall be based upon exposure to the material as an external radiation source.
Individual expo-sures to these materials shall be accounted for as part of the limitation on individual dose in 520.101.
These materials shall be subject to applicabic process and other engineering controls.
- 129 -
Amendment No.16
PROTECTION PROGlWI 6.11.2 In all operations in which adequate limitation of the inhalation of radioactive material by the use of process or other engineering controls is impracticable, the licensee may pennit an individual in a restricted area to use respiratory protective equipment to limit the inhalation of airborne radioactive material, provided:
a.
The limits specified in 6.11.1 above, are not exceeded, b.
Respiratory protective equipment is selected and used so that the peak concentrations of airborne radioactive material inhaled by an individual wearing the equipment do not exceed the pertinent concentration values specified in Appendix B, Tabic I, Column 1, of la CFR 20.
For the purposes of this subparagraph, the con-centration of radioactive material that is inhaled when respir-ators are worn may be determined by dividing the ambient airborne concentration by the protection factor specified in Tabic 6.11-1 for the respirator protective equipment worn.
If the intake of radioactivity is later determined by other measurements to have been different than that initially estimated, the later quantity shall be used in evaluating the exposures.
c.
The licensec advises each respirator user that he may leave the area at any time for relief from respirator use in case of equip-nent malfunction, physical or psychological discomfort, or any other condition that might cause reduction in the protection afforded the wearer.
d.
The licensee maintains a respiratory protective program adequate to assure that the requirements above are met and incorporates practices for respiratory protection consistent with those recommended by the American National Standards Institute (ANSI-Z88.2-1969). Such a program shall include:
1.
Air sampling and other surveys sufficient to identify the hazard, to evaluate individual exposures, and to permit proper selection of respiratory protective equipment.
2.
Written procedures to assure proper selection, supervision, and training of personnel using such protective equipment.
3.
Written procedures to assure the adequate fitting of respirators; and the testing of respiratory protective equipment for operability immediately prior to use.
4 Written procedures for maintenance to assure full effective-ness of respiratory protective equipment, including issuance, c1 caning and decontamination, taspection, repair, and storage.
Amendment No.16
- 130 -
i
5.
Written operational and administrative procedures for proper use of respiratory protective equipment including provisions for planned limitations on working times as necessitated by operational conditions.
6.
Bioassays and/or whole body counts of individuals (and other surveys, as appropriate) to evaluate individual exposures and to assess protection actually provided.
The licensee shall use equipment approved by the U.S. Bureau of e.
Mines under its appropriate Approval Schedules as set forth in Table 6.11-1.
Equipment not approved under U.S. Bureau of Mines Approval Schedules shall be used only if the licensee has evaluated the equipment and can demonstrate by testing, or on the basis of reliable test information, that the material and performanace characteristics of the equipment are at least equal to those afforded by U.S. Bureau of Mines approved eqcipment of the same type, as specified in Table 6.11.1.
f.
Unless otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified in Tabic 6.11-1 in selecting and using respiratory protective equipment.
REVOCATION 6.11.3 The specifications of Section 6.11 shall be revoked in their entirety upon adoption of the proposed change to 10 CFR 20, Section 20.103, which would make such provisions unnecessary.
Amendment No. 16
- 131 -
TABLE 6.11-1 f
PROTECTION FACTORS FOR RESPIRATORS a
PROTECTION FACTORS 2/
GUIDES TO SELECTION OF EQUIPMENT 5
PART'CULATES AND
~
BUREAU OF MINES / NATIONAL INSTITUTE VAPORS AND GASES FOR OCCUPATIONAL SAFETY AND llEALT11 se P
EXCEPT TRITIUM APPROVALS DESCRIPTION MODES 1/
OXIDE 3/
1.
AIR-PURIFYING RESPIRATORS Facepiece, half-mask 4/,
7/ NP S
30 CFR Part 11 Subpart K NP 100 30 CFR Part 11 Subpart K Facepiece, full 7/
~
~
II.
ATMOSPilERE-SUPPLYING RESPIRATOR 8
1.
Airline respirator
[;
Facepiece, llalf-mask CF 100 30 CFR Part 11 Subpart J Facepiece, Full CF 1,000 30 CFR Part 11 Subpart J to Facepiece, Full 7/
D 100 30 CFR Part 11 Subpart J Facepiece, Full PD 1,000 30 CFR Part 11 Subpart J llood CF S/
30 CFR Part 11 Subpart J Suit CF S/
6/
2.
Self-contained breathing apparatus (SCBA)
Facepiece, Full 7/
D 100 30 CFR Part 11 Subpart H Facepiece, Full PD 1,000 30 CFR Part 11 Subpart H Facepiece, Full R
100 30 CFR Part 11 Subpart !!
III. COMBINATION RESPIRATOR Any combination of air-Protection factor for purifying and atmosphere-type and mode of opera-30 CFR Part 11 11.63(b) supplying respirator tion as listed above.
TABLE 6.11-1 NOTES-
' l_/ See the followin6 symbols:
CF: Continuous Flow D: Demand NP:
Negative fressure (i.e., negative phase during inhalation)
PD:
Pressure Demand (i.e., always positive pressure)
R: Recirculating (closed circuit) 2/
(a) For purposes of this specification the protection factor is a measure of the degree of protection afforded by a respirator, defined as the ratio of the concentration of airborne radio-active material outside the respiratory protective equipment to that innide the equipment (usually inside the facepiece) under conditions of use.
It is applied to the ambient air-borne concentration to estimate the concentration inhaled by the wearer according to the following formula:
Ambient Airborne Concentration Concentration Inhaled =
Protection Factor (b) The protection factors apply:
(i) only for trained individuals wearing properly fitted respirators used and maintained under supervision in a well-planned respiratory protective program.
(ii) for air-purifying respirators only when high efficiency (above 99.9% removal efficiency by U.S. Bureau of M'ines type diocty3 phthalate (DOP) test) particulate filters and/or sorbents appropriate to the hazard are used in atmospheres not deficient in oxy 6en.
(iii) for atmosphere-supplying respirator's only when supplfed with adequate respirable air.
3/ Excluding radioactive contaminants that present an absorption or submersion hazard.
Fce tritium oxide approximately half of the in-take occurs by absorption through the skin so that an overall pro-tection factor of not more than approximately 2 is appropriate when atmosphere-supplyin6 respirators are used to protect against tritium oxide.
Air-purifying respirators are not recommended for use against tritium oxide.
See also footnote 5/, below, concerning supplied-air suits and hoods.
)] Under' chin type only.
Not recommended for use where it might be possible for the ambient airborne concentration to reach instanta-neous values Creater than 50 times the pertinent values in Appendix B, Table I, Column 1 of 10 CFR 20.
' I 33 -
Amendment No.16 n
5/ Appropriate protection factors must be determined taking account of the design of the suit or hood and its permeability to the contaminant under conditions of use.
No protection factor greater than 1,000 shall be used except as authorized by the Commission.
6/ No approval schedules currently available for this equipment.
Equip-ment must be evaluated by testing or on basis of available test information.
7/ Only for shaven faces.
NOTE 1:
Protection factors for respirators, as may be approved by the U. S. Bureau of Mines or the National Institute for Occupational Safety and !!calth according to approval schedules for respirators to protect against airborne radionuclides, oay be used to the extent that they do not exceed the protecticn factors listed in this Tabic.
The protection factors in tnis Table may not be ' appropriate to circumstances where chemical or other respiratory hazards exist in addition to radioactive hazards.
The selection and use of respirators for such circumstances should take into account approvals of the U. S.
Bureau of Mines or the National Institute for Occupational Safety and llealth in accordance with its applicable schedules.
NOTE 2: Radioactive contaminants for which the concentration values ir. Appendix B, Table I of 10 CFR part 20 are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations.
Under such circumstances, limitations on occupancy may have to be govern-ed by external dose limits.
1 l
l i
Amendment-No. 16
- 134 - (the next oage is 140)
_